An in situ diagnostic method for monitoring of fuel retention on the first wall under long-pulse operation of experimental advanced superconducting tokamak
An in situ diagnostic method for monitoring of fuel retention on the first wall under long-pulse operation of experimental advanced superconducting tokamak
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DOI：
10.1088/1402-4896/ab6005
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发表时间：
2020-01
期刊：
影响因子：
2.9
通讯作者：
Cong Li;Liying Sun;Zhenhua Hu;Dongye Zhao;Jiamin Liu;N. Gierse;D. Nicolai;Dingqing Wu;R. Hai;F. Ding;G. Luo;S. Brezinsek;C. Linsmeier;Yunfeng Liang;H. Ding
中科院分区：
文献类型：
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作者：
Cong Li;Liying Sun;Zhenhua Hu;Dongye Zhao;Jiamin Liu;N. Gierse;D. Nicolai;Dingqing Wu;R. Hai;F. Ding;G. Luo;S. Brezinsek;C. Linsmeier;Yunfeng Liang;H. Ding
等离子体-壁相互作用（PWI）研究是当前磁约束聚变装置长脉冲运行的一个活跃研究领域，如实验先进超导托卡马克（EAST）。迫切需要能够通过原位诊断方法来调查几个关键的PWI问题，例如燃料保留。本文提出了激光诱导击穿光谱（LIBS）与发射光谱（OES）相结合的原位诊断方法。整个系统用于研究PWI，填补了EAST长脉冲等离子体运行工况下燃料滞留与边缘等离子体状态相关性的研究空白。在EAST长脉冲等离子体运行过程中，同时监测了第一壁LIBS产生的燃料保留强度和OES产生的边缘等离子体状态。结果表明，氘(D)的保留量随着局部边缘D粒子通量的增加而增加。结果有效地证明了LIBS方法在即将到来的长脉冲聚变装置（如国际热核实验反应堆（ITER））中用于PWI研究的燃料保留原位调查的潜力。
Plasma-wall interaction (PWI) research is an active field of study in long-pulse operation in current magnetic confinement fusion devices, such as the Experimental Advanced Superconducting Tokamak (EAST). It is an urgent requirement to be able to investigate several key PWI issues, such as fuel retention, by in situ diagnostic methods. In this work, an in situ diagnostic method of laser-induced breakdown spectroscopy (LIBS) combined with optical emission spectroscopy (OES) is developed. The whole system is applied to study PWI and fill the research gap concerning the correlation between fuel retention and edge plasma conditions during long-pulse plasma operation conditions in EAST. The fuel retention intensity from LIBS on the first wall and the edge plasma condition from OES are monitored simultaneously during the long-pulse plasma operation in EAST. The results indicate that the deuterium (D) retention amount increases as the local edge D particle fluence increases. The results effectively demonstrate the potential of the LIBS method for in situ investigation of the fuel retention for PWI study in upcoming long-pulse fusion devices such as the International Thermonuclear Experimental Reactor (ITER).